Relevant bibliographies by topics / Reactores de fisión nuclear

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Reactores de fisión nuclear'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Reactores de fisión nuclear"

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Delepine, David, Edgar Casimiro Linares, José-Antonio Hernández Valencia, and Gerardo Moreno. "Uso de detectores de neutrinos para el monitoreo de reactores nucleares." Acta Universitaria 19, no. 3 (2009): 5–8. http://dx.doi.org/10.15174/au.2009.80.

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Se estudia la factibilidad del uso de los detectores de antineutrinos para el monitoreo de reactores nucleares. Usando un modelo sencillo de cascada de fisión a dos componentes, se ilustra la dependencia del número de antineutrinos detectados a una distancia L del reactor según la composición nuclear del combustible. Se explica el principio de detección de neutrinos de reactores en base al decaimiento beta inverso y se describe como los detectores de neutrinos pueden emplearse para el monitoreo de la producción de materiales fisibles en el reactor. Se comenta como generalizar este análisis al
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Sandoval Lagos, Jaime, and Edgar Mauricio López. "Desarrollo de capacidades para la operación del reactor nuclear IAN-R1." Revista Investigaciones y Aplicaciones Nucleares, no. 2 (December 17, 2018): 15–30. http://dx.doi.org/10.32685/2590-7468/invapnuclear.2.2018.52.

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Este documento presenta una descripción histórica del reactor nuclear de investigación IAN-R1. Se hace una contextualización sobre el origen del reactor en el marco del programa Átomos para la Paz, y se incluyen las características técnicas y la configuración inicial del núcleo, cuyo combustible nuclear de tecnología MTR (90%) fue sustituido por uno de tipo TRIGA (20%) (acrónimos de material testing reactor y training, research, isotopes general atomics, respectivamente). De igual manera, se presentan las características de las dos modernizaciones que se han realizado a la instrumentación y el
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Rockwell, Theodore. "Facts & Fission." Mechanical Engineering 131, no. 12 (2009): 32–37. http://dx.doi.org/10.1115/1.2009-dec-3.

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This article discusses the real-world practicality of nuclear power. Neither reactors nor casks of spent fuel have the capability of going “prompt critical” like a bomb. The laws of nature prohibit it and engineers must make clear that facts of nature are not matters of opinion. The Chernobyl reactor, which failed so spectacularly in Ukraine in 1986, became for many a symbol of the dangers represented by nuclear reactors. But that is not warranted; such an accident is simply impossible for the kind of commercial reactors now being planned or built. From a public safety standpoint, the most imp
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Kondylakis, J. S. "Theoretically and under very special applied conditions a nuclear fission reactor may explode as nuclear bomb." HNPS Proceedings 18 (November 23, 2019): 121. http://dx.doi.org/10.12681/hnps.2558.

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This article/presentation describes a theoretical and applied research in nuclear fission reactor systems. It concerns with theoretical approaches and in very special applied cases consideration where a common nuclear fission reactor system may be considered to explode as nuclear bomb. This research gives critical impacts to the design, operation, management and philosophy of nuclear fission reactors systems. It also includes a sensitivity analysis of a particular applied problem concerning the core melting of a nuclear reactor and its deposit to the bottom of reactor vessel. Specifically, in
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Naumov, Vadim, Sergey Gusak, and Andrey Naumov. "Small nuclear power plants for power supply in arctic regions: assessment of spent nuclear fuel radioactivity." Nuclear Energy and Technology 4, no. 2 (2018): 119–25. http://dx.doi.org/10.3897/nucet.4.30677.

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The purpose of the present study is the investigation of mass composition of long-lived radionuclides accumulated in the fuel cycle of small nuclear power plants (SNPP) as well as long-lived radioactivity of spent fuel of such reactors. Analysis was performed of the published data on the projects of SNPP with pressurized water-cooled reactors (LWR) and reactors cooled with Pb-Bi eutectics (SVBR). Information was obtained on the parameters of fuel cycle, design and materials of reactor cores, thermodynamic characteristics of coolants of the primary cooling circuit for reactor facilities of diff
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Ripani, M. "Energy from nuclear fission." EPJ Web of Conferences 246 (2020): 00010. http://dx.doi.org/10.1051/epjconf/202024600010.

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The physics of nuclear fission will be briefly illustrated, from the basic mechanism behind this phenomenon to the relevant physical quantities like nuclear cross sections, neutron flux and reaction products, together with the accompanying phenomenon of neutron capture and its role in determining how the fuel transforms in a nuclear reactor. The basic concepts underlying the operation of different types of nuclear reactors will be illustrated, along with the concept of fuel cycle. After touching on the aspect of safety, the current situation of nuclear power in the world, with its costs, its r
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Ruskov, Ivan, Andrei Goverdovski, Walter Furman, et al. "Neutron induced fission of 237Np – status, challenges and opportunities." EPJ Web of Conferences 169 (2018): 00021. http://dx.doi.org/10.1051/epjconf/201816900021.

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Nowadays, there is an increased interest in a complete study of the neutron-induced fission of 237Np. This is due to the need of accurate and reliable nuclear data for nuclear science and technology. 237Np is generated (and accumulated) in the nuclear reactor core during reactor operation. As one of the most abundant long-lived isotopes in spent fuel (“waste”), the incineration of 237Np becomes an important issue. One scenario for burning of 237Np and other radio-toxic minor actinides suggests they are to be mixed into the fuel of future fast-neutron reactors, employing the so-called transmuta
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Chavez-Estrada, Marisol, and Alexis A. Aguilar-Arevalo. "Antineutrino Flux from the Laguna Verde Nuclear Power Plant." Advances in High Energy Physics 2015 (2015): 1–9. http://dx.doi.org/10.1155/2015/109738.

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We present a calculation of the antineutrino flux produced by the reactors at the Laguna Verde Nuclear Power Plant in México, based on the antineutrino spectra produced in the decay chains of the fission fragments of the main isotopes in the reactor core, and their fission rates, which have been calculated using the DRAGON simulation code. We also present an estimate of the number of expected events in a detector made of plastic scintillator with a mass of 1 ton, at 100 m from the reactor cores.
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Till, Charles E. "Nuclear fission reactors." Reviews of Modern Physics 71, no. 2 (1999): S451—S455. http://dx.doi.org/10.1103/revmodphys.71.s451.

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Hidaka, Hiroshi. "A Review of In Situ Isotopic Studies of the Oklo and Bangombé Natural Fission Reactors Using Microbeam Analytical Techniques." Minerals 10, no. 12 (2020): 1060. http://dx.doi.org/10.3390/min10121060.

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Isotopic analyses of elements in the natural reactor materials have often been performed to understand the distribution behaviors of the fission products and to evaluate the function of nuclear reactions since the first discovery of a natural reactor in 1972. Several types of unique microminerals, including significant amounts of fission products, have been found in and around the Oklo and the Bangombé natural reactors. In the past two decades, microbeam techniques using ion and laser probe facilities have been effectively applied for the in situ isotopic analyses of individual microminerals t
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Dissertations / Theses on the topic "Reactores de fisión nuclear"

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García, Fajardo Laura. "DISEÑO CONCEPTUAL DE UN SISTEMA CONTROLADO POR UN ACELERADOR PARA TRANSMUTACIÓN DE RESIDUOS NUCLEARES Y APLICACIONES ENERGÉTICAS." Doctoral thesis, Universitat Politècnica de València, 2012. http://hdl.handle.net/10251/17654.

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Las posibilidades de desarrollo de la energía nuclear aumentan considerablemente con el incremento de la demanda energética mundial. Sin embargo, el manejo de los residuos provenientes del combustible nuclear gastado de las plantas nucleares convencionales es actualmente uno de los principales problemas que enfrenta el uso de esta fuente de energía. El objetivo del presente trabajo consistió en realizar el diseño conceptual del TADSEA (Transmutation Advanced Device for Sustainable Energy Applications): un sistema controlado por un acelerador (ADS), de tipo lecho de bolas, refrigerado por helio
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Sánchez, Velasco Francisco Javier. "Experimental characterization of aerosol retention in the break stage of a dry steam generator in SGTR sequences." Doctoral thesis, Universitat Politècnica de València, 2008. http://hdl.handle.net/10251/3839.

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En reactores de agua a presión, las secuencias de accidente severo con rotura de tubos del generador de vapor (conocidas por sus siglas en inglés SGTR, Steam Generator Tube Rupture) son dominantes del riesgo, a pesar de ser sucesos de muy baja probabilidad. Su importancia reside en la potencial liberación de radiactividad, en forma de aerosol, que supondrían desde el circuito primario al medio ambiente, sin intervención de la contención. Sin embargo, las partículas radioactivas podrían retenerse parcialmente en el secundario del generador de vapor aun cuando no quedara agua en el mismo. La aus
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Kingdon, David Ross. "Safety characteristics of a suspended-pellet fission reactor system." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1998. http://www.collectionscanada.ca/obj/s4/f2/dsk1/tape11/PQDD_0001/NQ42856.pdf.

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Stewart, Christopher L. "Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor." Thesis, Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50407.

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The SABR fusion-fission hybrid concept for a fast burner reactor, which combines the IFR-PRISM fast reactor technology and the ITER tokamak physics and fusion technology, is adapted for a fusion-fission hybrid reactor, designated SABrR. SABrR is a sodium-cooled 3000 MWth reactor fueled with U-Pu-10Zr. For the chosen fuel and core geometry, two configurations of neutron reflector and tritium breeding structures are investigated: one which emphasizes a high tritium production rate and the other which emphasizes a high fissile production rate. Neutronics calculations are performed using the ER
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Martin, Jerry Lynn. "DABLE--a facility for measuring fission product transport in gas-cooled reactors." Thesis, Massachusetts Institute of Technology, 1991. http://hdl.handle.net/1721.1/13906.

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Sweeney, David J. "Reactor power history from fission product signatures." Thesis, [College Station, Tex. : Texas A&M University, 2008. http://hdl.handle.net/1969.1/ETD-TAMU-3209.

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Presby, Andrew L. "Thermophotovoltaic energy conversion in space nuclear reactor power systems." Thesis, Monterey, Calif. : Naval Postgraduate School, 2004. http://edocs.nps.edu/npspubs/scholarly/theses/2004/Dec/04Dec%5FPresby.pdf.

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Thesis (Astronautical Engineer and M. S. in Astronautical Engineering)--Naval Postgraduate School, December 2004.<br>Thesis Advisor(s): Gopinath, Ashok ; Michael, Sherif. "December 2004." Description based on title screen as viewed on March 13, 2009. Includes bibliographical references (p. 123-127). Also available in print.
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Mauer, Andrew N. "A superconducting fusion transmutation of waste reactor." Thesis, Georgia Institute of Technology, 2002. http://hdl.handle.net/1853/15970.

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Sommer, Christopher Michael. "Subcritical transmutation of spent nuclear fuel." Diss., Georgia Institute of Technology, 2011. http://hdl.handle.net/1853/41205.

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A series of fuel cycle simulations were performed using CEA's reactor physics code ERANOS 2.0 to analyze the transmutation performance of the Subcritical Advanced Burner Reactor (SABR). SABR is a fusion-fission hybrid reactor that combines the leading sodium cooled fast reactor technology with the leading tokamak plasma technology based on ITER physics. Two general fuel cycles were considered for the SABR system. The first fuel cycle is one in which all of the transuranics from light water reactors are burned in SABR. The second fuel cycle is a minor actinide burning fuel cycle in which al
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Taylor, Neil Rutger. "Analysis of a High Temperature Fission Chamber Experiment for Next Generation Reactors." The Ohio State University, 2017. http://rave.ohiolink.edu/etdc/view?acc_num=osu1512048679402356.

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Books on the topic "Reactores de fisión nuclear"

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Nuclear fission reactors. Facts on File, 2011.

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Nuclear reactor physics. 2nd ed. Wiley-VCH, 2007.

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McIntosh, W. W. Nuclear power reactors, an overview. Science and Technology, Washington State Institute for Public Policy, 1985.

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Charles, Pierre. Energie nucléaire: Fission et fusion. Ellipses, 2007.

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Italy) International Workshop on Fusion Neutrons and Subcritical Nuclear Fission (2011 Varenna. Fusion for neutrons and subcritical nuclear fission: Proceedings of the international conference : Varenna, Italy, 12-15 September 2011. Edited by Källne Jan. American Institute of Physics, 2012.

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Lamaze, George P. Activation foil irradiation by reactor cavity fission sources. U.S. Dept. of Commerce, National Bureau of Standards, 1988.

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Symposium, E. on Nuclear Materials for Fission Reactors (1991 Strasbourg France). Nuclear materials for fission reactors: Proceedings of Symposium E on Nuclear Materials for Fission Reactors of the 1991 E-MRS Fall Conference, Strasbourg, France, November 4-7, 1991. North-Holland, 1992.

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Viswanathan, U. K. Measurement of fission gas release from irradiated nuclear fuel elements. Bhabha Atomic Research Centre, 2005.

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International School of Physics "Enrico Fermi" (1990 Varenna, Italy). Status and perspectives of nuclear energy: Fission and fusion : Varenna on Lake Como, Villa Monastero, 10-20 July 1990. North-Holland, 1992.

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Slugeň, Vladimír. Safety of VVER-440 reactors: Barriers against fission products release. Springer, 2011.

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Book chapters on the topic "Reactores de fisión nuclear"

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Till, Charles E. "Nuclear Fission Reactors." In More Things in Heaven and Earth. Springer New York, 1999. http://dx.doi.org/10.1007/978-1-4612-1512-7_50.

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Natelson, Michael. "Fission Reactor Physics." In Nuclear Energy. Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-5716-9_2.

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Natelson, Michael. "Fission Reactor Physics." In Nuclear Energy. Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_18.

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Glasstone, Samuel, and Alexander Sesonske. "Energy From Nuclear Fission." In Nuclear Reactor Engineering. Springer US, 1994. http://dx.doi.org/10.1007/978-1-4615-7525-2_1.

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Glasstone, Samuel, and Alexander Sesonske. "Energy from Nuclear Fission." In Nuclear Reactor Engineering. Springer US, 1994. http://dx.doi.org/10.1007/978-1-4899-5751-1_1.

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Krishnan, L. V. "Oklo Natural Fission Reactor." In Nuclear Energy Encyclopedia. John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch7.

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McFarlane, Harold. "Introduction to Generation-IV Fission Reactors." In Nuclear Energy Encyclopedia. John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch25.

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Tsvetkov, Pavel V. "Graphite-Moderated Fission Reactor Technology." In Nuclear Energy Encyclopedia. John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch20.

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Masterson, Robert E. "Nuclear Fission and Nuclear Energy Production." In Introduction to Nuclear Reactor Physics. CRC Press, 2017. http://dx.doi.org/10.1201/9781315118055-7.

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Marques, J. G. "Review of Generation-III/III+ Fission Reactors." In Nuclear Energy Encyclopedia. John Wiley & Sons, Inc., 2011. http://dx.doi.org/10.1002/9781118043493.ch22.

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Conference papers on the topic "Reactores de fisión nuclear"

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Nichols, D. M., J. C. Boyington, Y. Cheng, et al. "Reactor Pulse Tracking using Micro-Pocket Fission Detectors in Research Reactors." In 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC). IEEE, 2019. http://dx.doi.org/10.1109/nss/mic42101.2019.9059692.

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Pahladsingh, Remond R. "Possibility of Using Gamma Radiation From HTR Reactors for Processing of Food and Medical Products." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49316.

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During the fission process in most of the presently operating nuclear reactors nuclear energy is converted into thermal energy and transferred to common steamcycles for powergeneration. As part of the fission process also α-, β- and neutrons particles are released from the nucleus; the release of gamma-rays is also a part of the fission process. In present nuclear reactors α-, β-, neutrons particles and particularly Gamma-rays are not gainfully used as a result of the reactor design and of the containment. These plants are built as required by regulations and international standards for safety
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Zang, Xiaochuan, and Tao Liu. "Study on Emergency Action Levels of the Modular High Temperature Gas-Cooled Reactor." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67583.

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The emergency action level (EAL) scheme for a modular high temperature gas-cooled reactor (HTR) plant refers to the generic EAL development guidance for pressurized water reactors (PWR) with HTR modification due to its design issues. Based on reactor’s accidents analysis and consequence assessment, EAL scheme of HTR is established through the steps of category and classification. Four emergency classes are set for HTR consisting of U (Emergency Standby), A (Facilities Emergency), S (Site Area Emergency) and G (General Emergency). The Recognition Category of Initiating Condition (IC) and EAL co
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Clark, Rodney, and Robert Sheldon. "Dusty Plasma Based Fission Fragment Nuclear Reactor." In 41st AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit. American Institute of Aeronautics and Astronautics, 2005. http://dx.doi.org/10.2514/6.2005-4460.

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Bouchard, Jacques. "Nuclear data for innovative fission reactors and fuel cycles." In International Conference on Nuclear Data for Science and Technology. EDP Sciences, 2007. http://dx.doi.org/10.1051/ndata:07718.

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Zhanbo, Wang. "Nuclear Fission in Fast Breeder Reactors and Its Sustainability." In 7th International Conference on Education, Management, Information and Computer Science (ICEMC 2017). Atlantis Press, 2017. http://dx.doi.org/10.2991/icemc-17.2017.183.

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Sagara, Hiroshi, Tadashi Yoshida, and Masaki Saito. "Characterization of Individual Fission Products in Terms of Their Production and Transmutation." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22753.

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In order to establish a simple and common basis which can be referred for the specific studies on the fission products (FP) transmutation and its strategies, the general characteristics of the dominant individual FPs in terms of their production and transmutation in the fast reactor have been studied with an ideal model in the present paper. The potential hazard of each nuclide in long-term utilization of nuclear energy in human society has been quantitatively evaluated. During utilization of fission energy, two short half-life FPs, 90Sr and 137Cs, almost determine the total toxicity of FP nuc
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Tsvetkov, Pavel V., and Theodore A. Parish. "Conceptual Analysis of Fission Fragment Magnetic Collimator Reactors." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22089.

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As part of the current research work within the US DOE NERI Direct Electricity Conversion (DEC) Project on methods for utilizing direct electricity conversion in nuclear reactors, a detailed study of a Fission Fragment Magnetic Collimator Reactor (FFMCR) has been performed. The FFMCR concept is an advanced DEC system that combines advantageous design solutions proposed for application in both fission and fusion reactors. The present study was focused on determining the electrical efficiency and other important operational aspects of the FFMCR concept. In principle, acceptable characteristics h
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Cash, Jamie, Gary Rochau, Donald King, and Charles Morrow. "Conceptual Analysis of Criticality Aspects of Fission Electric Cell Reactors." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22545.

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The U.S. Department of Energy’s Nuclear Energy Research Initiative Direct Energy Conversion project has a goal of developing direct energy conversion (DEC) processes suitable for commercial development. DEC is any fission process that returns usable energy with no intermediate thermal process. This project includes the study of the fission electric cell (FEC). In the FEC, fission fragments exit the fuel element cathode and are collected by the cell anode. Previous work [1] has shown the potential of FECs with theoretical efficiencies up to 60%. Inspection of this work indicates the need for ad
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Vijayakumaran, P. M., C. P. Nagaraj, C. Paramasivan Pillai, R. Ramakrishnan, and M. Sivaramakrishna. "Nuclear Instrumentation Systems in Prototype Fast Breeder Reactor." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49354.

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The nuclear instrumentation systems of the Prototype Fast Breeder Reactor (PFBR) primarily comprise of global Neutron Flux Monitoring, Failed Fuel Detection &amp; Location, Radiation Monitoring and Post-Accident Monitoring. High temperature fission chambers are provided at in-vessel locations for monitoring neutron flux. Failed fuel detection and location is by monitoring the cover gas for fission gases and primary sodium for delayed neutrons. Signals of the core monitoring detectors are used to initiate SCRAM to protect the reactor from various postulated initiating events. Radiation levels i
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Reports on the topic "Reactores de fisión nuclear"

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Okrent, D. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report. Office of Scientific and Technical Information (OSTI), 1997. http://dx.doi.org/10.2172/541929.

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Bartram, B. W., and D. K. Dougherty. A long term radiological risk model for plutonium-fueled and fission reactor space nuclear system. Office of Scientific and Technical Information (OSTI), 1987. http://dx.doi.org/10.2172/6120678.

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Weston, L. W. (Temperature coefficient of U-235 fueled thermal reactors and nuclear data on eta at thermal neutron energies and 239-Pu fission cross sections between 1 and 100 keV). Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6354623.

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